Double PN Benchmark for the One-Dimensional Plane Geometry Monoenergetic Neutron Transport Equation with Anisotropic Scatter.

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Title: Double PN Benchmark for the One-Dimensional Plane Geometry Monoenergetic Neutron Transport Equation with Anisotropic Scatter.
Authors: Ganapol, B. D.1 (AUTHOR) ganapol@cowboy.ame.arizona.edu, Mostacci, D.2 (AUTHOR)
Source: Nuclear Science & Engineering. Apr2026, Vol. 200 Issue 4, p766-780. 15p.
Subjects: Neutron transport theory, Plane geometry, Transfer matrix, Fast neutrons, Matrices (Mathematics), Scattering (Physics), Approximation error
Abstract: This presentation concerns the development of yet another benchmark in a series for solution of the linear neutron transport equation, but using the Double PN (DPN) approximation. As more and more numerical and analytical solutions to the linear particle transport equation appear, their verification becomes increasingly important. There are numerous ways of solving the one-dimensional monoenergetic neutron transport equation in plane geometry, where PN and DPN methods play a prominent role. Here, a new method of solution, based on matrix algebra and scaling to avoid overflows and leading to a response matrix solution, is derived and demonstrated for a highly anisotropically scattering medium with a beam source impinging on a scattering and absorbing slab medium. [ABSTRACT FROM AUTHOR]
Copyright of Nuclear Science & Engineering is the property of Taylor & Francis Ltd and its content may not be copied or emailed to multiple sites without the copyright holder's express written permission. Additionally, content may not be used with any artificial intelligence tools or machine learning technologies. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
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An: 192312467
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  Data: Double PN Benchmark for the One-Dimensional Plane Geometry Monoenergetic Neutron Transport Equation with Anisotropic Scatter.
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  Data: <searchLink fieldCode="AR" term="%22Ganapol%2C+B%2E+D%2E%22">Ganapol, B. D.</searchLink><relatesTo>1</relatesTo> (AUTHOR)<i> ganapol@cowboy.ame.arizona.edu</i><br /><searchLink fieldCode="AR" term="%22Mostacci%2C+D%2E%22">Mostacci, D.</searchLink><relatesTo>2</relatesTo> (AUTHOR)
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  Data: <searchLink fieldCode="JN" term="%22Nuclear+Science+%26+Engineering%22">Nuclear Science & Engineering</searchLink>. Apr2026, Vol. 200 Issue 4, p766-780. 15p.
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  Data: <searchLink fieldCode="DE" term="%22Neutron+transport+theory%22">Neutron transport theory</searchLink><br /><searchLink fieldCode="DE" term="%22Plane+geometry%22">Plane geometry</searchLink><br /><searchLink fieldCode="DE" term="%22Transfer+matrix%22">Transfer matrix</searchLink><br /><searchLink fieldCode="DE" term="%22Fast+neutrons%22">Fast neutrons</searchLink><br /><searchLink fieldCode="DE" term="%22Matrices+%28Mathematics%29%22">Matrices (Mathematics)</searchLink><br /><searchLink fieldCode="DE" term="%22Scattering+%28Physics%29%22">Scattering (Physics)</searchLink><br /><searchLink fieldCode="DE" term="%22Approximation+error%22">Approximation error</searchLink>
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  Label: Abstract
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  Data: This presentation concerns the development of yet another benchmark in a series for solution of the linear neutron transport equation, but using the Double PN (DPN) approximation. As more and more numerical and analytical solutions to the linear particle transport equation appear, their verification becomes increasingly important. There are numerous ways of solving the one-dimensional monoenergetic neutron transport equation in plane geometry, where PN and DPN methods play a prominent role. Here, a new method of solution, based on matrix algebra and scaling to avoid overflows and leading to a response matrix solution, is derived and demonstrated for a highly anisotropically scattering medium with a beam source impinging on a scattering and absorbing slab medium. [ABSTRACT FROM AUTHOR]
– Name: AbstractSuppliedCopyright
  Label:
  Group: Ab
  Data: <i>Copyright of Nuclear Science & Engineering is the property of Taylor & Francis Ltd and its content may not be copied or emailed to multiple sites without the copyright holder's express written permission. Additionally, content may not be used with any artificial intelligence tools or machine learning technologies. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract.</i> (Copyright applies to all Abstracts.)
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      – Type: doi
        Value: 10.1080/00295639.2024.2423130
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      – Code: eng
        Text: English
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      Pagination:
        PageCount: 15
        StartPage: 766
    Subjects:
      – SubjectFull: Neutron transport theory
        Type: general
      – SubjectFull: Plane geometry
        Type: general
      – SubjectFull: Transfer matrix
        Type: general
      – SubjectFull: Fast neutrons
        Type: general
      – SubjectFull: Matrices (Mathematics)
        Type: general
      – SubjectFull: Scattering (Physics)
        Type: general
      – SubjectFull: Approximation error
        Type: general
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      – TitleFull: Double PN Benchmark for the One-Dimensional Plane Geometry Monoenergetic Neutron Transport Equation with Anisotropic Scatter.
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              M: 04
              Text: Apr2026
              Type: published
              Y: 2026
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